ML17013A460

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Susquehanna - Draft - Outlines (Folder 2)
ML17013A460
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 11/14/2016
From:
Operations Branch I
To:
Susquehanna
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ML16076A438 List:
References
U01931
Download: ML17013A460 (28)
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Appendix D Scenario Outline Form ES-D-1 Facility:

SSES Unit 1 And 2 Scenario No.: 1 Op-Test No.: LOC28 Examiners:

Operators:

Initial Conditions:

Unit 1 is at 95 % gower for a rod control gattern adjustment at EOL. HPCI is out of service. The 'E' EOG is substituted for 'A' EOG. Turnover:

Swag 'A' RFP main lube oil gumgs . RFP lube oil conditioner swagged from 'A' to 'B' last shift. Severe thunderstorm watch is in effect for Luzerne County. Event Malf. Event Event No. No. Type* Description 1 N/A N Swap 'A' RFP main lube oil pumps SRO,BOP (OP-145-003) 2 N/A R Withdraw control rods to raise reactor power 3 percent. SRO, ATC (OP-A0-338, G0-100-012) mfFW145 'B' RFPT trips on high vibration, Recirc LIM2 runback, Setup for 3 0078 N/A event4 (AR-101-A16, ON-164-002) cmfTR03_ I (TS) APRM 2 and 3 'A' Recirc Loop drive flow fails high during LIM2 4 FTB31 1N014C SRO.ATC runback (TS 3.3.1.1) cmfAV04_ C (TS) RBCCW TCV fails, ESW placed in-service to restore RBCCW 5 TV11028 SRO,BOP cooling (ON-RBCCW-101

), ESW loop declared inoperable when alianed to RBCCW <TS 3.7.2) 6 mfRW1140 c RBCCW rupture on the common discharge header. 'A' RRP 01 f:20 SRO.ATC temperature rises raipidly requiring a manual Scram 7 mfRD155 M Hydraulic-block ATWS 017 All (E0-100-113, OP-145-005, ES-158-002) cmfPM03 -SLC pump trips after start, standby SLC pump successfully injects 8 1P208A c cmfPM03_ SRO,BOP boron (OP-153-001) 1P208B 9 cmfTR01 I Wide Range level instrument fails, RFP flow must be raised to LT14201A SRO,ATC maintain reactor level in ATWS band 10 mfFW148 c In-service RFPT trips after first scram, RCIC restored to maintain 002 All RPV level while standby RFPT placed in-service

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section Scenario Events Actual D.5.d) Attributes
1. Malfunctions after EOP entry (1-2) 8,9,10 3 2. Abnormal events (2-4) 4,5,6 3 3. Major transients (1-2) 7 1 4. EOPs entered/requiring substantive actions (1-2) E0-000-102 1 5. EOP contingencies requiring substantive actions (0-2) E0-000-113 1 6. EOP based Critical tasks (2-3) 3 CT-1 Inject SLC CT-2 Lowers RPV level to <-60" but >-161" CT-3 Inserts control rods IAW E0-000-113 Appendix D Scenario Outline Form ES-D-1 Facility:

SSES Units 1 and 2 Scenario No.: 3 Op-Test No.: LOC28 Examiners:

Operators:

Initial Conditions:

Unit 1 is at 33% (2ower shutting down for RCS leakage at EOL. Turnover:

Insert Control Rods and test Turbine By(2ass valve #3 for valve functional testing. Event Malf. Event Event No. No. Type* Description 1 N/A N Test turbine bypass valve #3 SRO,BOP (S0-182-001) 2 N/A R Insert control rods SRO,ATC (OP-156-001, OP-A0-338) cmfHX02_ C (TS) FW heater 2C tube leak (AR-120-C10, 010), Isolate FW heater 3 1E102C SRO,BOP extraction steam (ON-147-002), TS MCPR limits not applicable (TS 3.2.2) cmfEB01 -4 1A203 I (TS) ESS Bus 1 C lockout, Orywell leak severity rises, reactor scram mfRR164 SRO,ATC required (ON-4KV-101, TS 3.8.7) 010 5 mfRP158 c Electrical ATWS (E0-000-113) 003 All ARI inserts control rods 6 cmfMV06 I RCIC injection valve fails to auto open on initiation HV149FOfa SRO,BOP (OP-150-001) 7 mfRR179 c Fuel failure with high MSL radiation, MSIV isolation required 003 All (AR-103-001, AR-104-001) cmfMV01 HPCI steam isolation valves fail to automatically close (AR-114-8 HV155F002 I F04, F05}, manual isolation successful after reactor pressure cmfMV07 SRO,BOP HV155F003 reduced 9 mfRC150 M Unisolable RCS leak into Secondary Contrainment, 2 areas above 004 All Max Safe Temp (E0-000-104)

  • (N}ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section Scenario Events Actual 0.5.d) Attributes
1. Malfunctions after EOP entry (1-2) 6,7,8 3 2. Abnormal events (2-4) 3,4,5 3 3. Major transients (1-2) 9 1 4. EOPs entered/requiring substantive actions (1-2) E0-000-102 2 E0-000-104
5. EOP contingencies requiring substantive actions (0-2) E0-000-113 2 E0-000-112
6. EOP based Critical tasks (2-3) CT-1 Manually initiate ARI CT-2 Emergency Depressurize the reactor when two 2 Secondary Containment Areas exceed Max Safe Temp levels Appendix D Scenario Outline Form ES-D-1 Facility:

SSES Units 1 and 2 Scenario No.: 4 Op-Test No.: LOC28 Examiners:

Operators:

Initial Conditions:

Unit 1 is at 90% gower. RCIC is out of Service. OBE in Lehigh Valle)'..

ON-NATPHENOM-001 is comglete.

Unit 2 is at rated gower. Turnover:

Shutdown the 'B' EDG, the 15-min run at 1 OOOKW is comglete.

Raise gower 5% with Recirc flow IAW the RMR. __ nt Malf. Event Event No. No. Type* Description 1 N/A N Secure 'B' EDG SRO,BOP (S0-024-001 B) 2 N/A R C(TS) Raise Reactor Power 5% using Recirc flow, RRP runaway SRO,ATC mfRD155 C (TS) Control rod drift in/out 3 0085023 0055023 SRO.ATC (TS 3.1.3) 4 mfDS003 C (TS) Startup Transformer 20 lockout 008 SRO.BOP (TS 3.8.1) 5 mfMS183 M Small RCS steam leak in the Drywell 007 All 6 Various I HPCI fails to automatically initiate on high Drywell pressure, all SRO,BOP other high-pressure injection lost 7 mfRH149 c Stem-to-disk separation of RHR F016 Drywell Spray valve 011A(B) SRO,BOP 8 Various M Loss of reactor level indication

-RPV Flooding All (E0-000-114)

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section Scenario Events Actual D.5.d) Attributes
1. Malfunctions after EOP entry (1-2) 6,7 2 2. Abnormal events (2-4) 3,4 2 3. Major transients (1-2) 5, 8 2 4. EOPs entered/requiring substantive actions (1-2) E0-000-102 2 E0-000-103
5. EOP contingencies requiring substantive actions (0-2) E0-000-114 1 6. EOP based Critical tasks (2-3) CT-1 Spray the Drywell when Suppression Chamber pressure exceeds 13 psig 2 CT-2 Performs RPV Flooding when RPV water level becomes indeterminate by establishing RPV Flooded to Steamlines ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Susquehanna Date of Examination:

11/14/2016 Examination Level: RO x SRO Operating Test Number: U01931 Administrative Topic (see Note) Type Describe activity to be performed Code* Complete Aborted Evolution Log Conduct of Operations D,R Perform LPRM Upscale Alarm Tracking Conduct of Operations D,R Perform Jet Pump Operability Check Equipment Control R,N Radiation Control Activate Fire Brigade Emergency Plan S,D NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items). *Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:::;; 3 for ROs; :::;; 4 for SROs & RO retakes) (N)ew or (M)odified from bank (;:: 1) (P)revious 2 exams (:::;; 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Susquehanna Date of Examination:

11/14/2016 Examination Level: RO SRO K Operating Test Number: U01931 Administrative Topic (see Note) Type Describe activity to be performed Code* Perform Validation of Heat Balance Conduct of Operations R,M Perform LPRM Upscale Alarm Operability Tracking Conduct of Operations R,D and Determine Required Actions Determine Operability ofMSIV Isolation Actuation Equipment Control R,D Determine LCO Applicability and Ability to Bypass Radiation Control R,D Secondary Containment Zone 2 Isolation Classify an Emergency Condition and Complete Emergency Plan R,N Emergency Notification Report NOTE: All items (five total) are required for SROs. RO applicants require only four items .unless they are retaking only the administrative topics (which would require all five items). *Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; ::; 4 for SROs & RO retakes) (N)ew or (M)odified from bank 1) (P)revious 2 exams (S 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Susguehanna Date of Examination:

11/14/2016 Exam Level: RO x SRO-I SRO-U Operating Test No.: U01931 Control Room Systems:*

8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code* Safety Function a. Reset Recirc Lim 2 Runback -64.0N.67049.101 M,S 1 b. Reactor Feed Pump Post Scram Recovery-45.0P.21388.102 L,M,S 2 c. Open MSIVs during Reactor SIU (All rods in) -84.0P.24666.151 A,D,EN,L,S 3 d. Shutdown Cooling Temperature Control -49.0N.20294.151 A,M,L,S,P 4 e. Re-establish RBHVAC IAW ES-134-003

-34.E0.20802.151 A,D,EN,L,S 5 f. Energize Dead 4KV ESS Bus 2D -04.0N.20641.251 A,D,S 6 g. APRM Gain Adjust -78.0P.27731.101 D,P,S 7 h. Place Alternate TBCCW Pump l/S -15.0P.20688.151 A,D,P,S 8 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Hydraulically Remove HCU from Service -55.0P.003.102 D,R 1 j. Start RPS MG Set 2S237A Locally-58.0P.26824.201 D,R 7 k. Place RHR in SPC at RSDP -49.0P.1877.201 D,E,R 5

  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room. *Type Codes Criteria for RO I SRO-I / SRO-U (A)lternate path 4-6 14-612-3 (C)ontrol room (D)irect from bank :::;9/:::;8/:::;4 (E)mergency or abnormal in-plant <:1/<:1/<:1 (EN)gineered safety feature <:1 I <:1 I<: 1 (control room system) (L)ow-Power I Shutdown <:1/<:1/<:1 (N)ew or (M)odified from bank including 1 (A) <:2/<:2/<:1 (P)revious 2 exams :::; 3 /:::; 3 /:::; 2 (randomly selected) (R)CA <:1/<:1/<:1 (S)imulator ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Susquehanna Date of Examination:

11/14/2016 Exam Level: RO SRO-I x SRO-U Operating Test No.: U01931 Control Room Systems:*

8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code* Safety Function a. Reset Recirc Lim 2 Runback, -64.0N.67049.101 M,S 1 b. Reactor Feed Pump Post Scram Recovery-45.0P.21388.102 L,M,S 2 c. Open MSIVs during Reactor S/U (All rods in) -84.0P.24666.151 A,D,EN,L,S 3 d. Shutdown Cooling Temperature Control -49.0N.20294.151 A,M,L,S,P 4 e. Re-establish RBHVAC IAW ES-134-003-34.E0.20802.151 A,D,EN,L,S 5 f. Energize Dead 4KV ESS Bus 2D -04.0N.20641.251 A,D,S 6 g. h. Place Alternate TBCCW Pump l/S-15.0P.20688.151 A,D,P,S 8 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Hydraulically Remove HCU from Service -55.0P.003.102 D,R 1 j. Start RPS MG Set 2S237A Locally-58.0P.26824.201 D,R 7 k. Place RHR in SPC at RSDP -49.0P.1877.201 D,E,R 5

  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room. *Type Codes Criteria for RO I SRO-I / SRO-U (A)lternate path 4-614-612-3 (C)ontrol room (D)irect from bank :S9/:S8/:S4 (E)mergency or abnormal in-plant <::1/<::1/<::1 (EN)gineered safety feature <::1 I <::1 I<:: 1 (control room system) (L)ow-Power I Shutdown <::1/<::1/<::1 (N)ew or (M)odified from bank including 1 (A) <::2/<::2/<::1 (P)revious 2 exams :::; 3 I:::; 3 I:::; 2 (randomly selected) (R)CA <::1/<::1/<::1 (S)imulator ES-401 Facility:

SSES LOC28 NRC Tier Group K K K 1 2 3 1. 1 3 4 3 Emergency

& 2 1 2 1 Plant Tier Evolutions Totals 4 6 4 1 3 2 3 2. Plant 2 1 0 2 Systems Tier Totals 4 2 5 Written Examination Outline I Date of Exam: November 2016 RO KIA Category Points K K K A A A A G 4 5 6 1 2 3 4

  • Total ..

3 4 *: . 3 20 I*** .. .... ' .*. :. . ... :***. 1 1 1 7 **** ** '*:* .. ** 4 5 4 27 .* I* 2 2 2 3 2 2 2 3 26 2 1 1 1 1 1 1 1 12 4 3 3 4 3 3 3 4 38 Form ES-401-1 SRO-Only Points A2 G* Total 3 4 7 2 1 3 5 5 10 3 2 5 0 1 2 3 4 4 8 3. Generic Knowledge

& Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 3 3 2 2 2 2 1 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two). (One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from another Tier 3 Category.)

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted with justification; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7. The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIAs. 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (I Rs) for the applicable license level, and the point totals(#)

for each system and category.

Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#)

on Form ES-401-3.

Limit SRO selections to KIAs that are linked to 10 CFR 55.43. G* Generic KIAs ES-401 2 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions

-Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) EA2.02 -Ability to determine and/or 295030 Low Suppression Pool x interpret the following as they apply to Water Level I 5 LOW SUPPRESSION POOL WATER LEVEL: Suppression pool temperature AA2.01 -Ability to determine and/or 295006 SCRAM / 1 x interpret the following as they apply to SCRAM: Reactor power AA2.01 -Ability to determine and/or 295004 Partial or Complete interpret the following as they apply to x PARTIAL OR COMPLETE LOSS OF Loss of DC Power I 6 D.C. POWER: Cause of partial or complete loss of D.C. power 2.2.44 -Equipment Control: Ability to interpret control room indications to 295038 High Off-site Release x verify the status and operation of a Rate 19 system, and understand how operator actions and directives affect plant and system conditions.

2.4.9 -Emergency Procedures I Plan: 295025 High Reactor Pressure I Knowledge of low power I shutdown 3 x implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

295026 Suppression Pool High 2.2.22 -Equipment Control: Knowledge Water Temperature I 5 x of limiting conditions for operations and safety limits. 2.4.47 -Emergency Procedures I Plan: 295018 Partial or Complete Ability to diagnose and recognize trends Loss of CCW I 8 x in an accurate and timely manner utilizing the appropriate control room reference material.

AK1 .02 -Knowledge of the operational implications of the following concepts as 700000 Generator Voltage and x they apply to GENERA TOR VOLTAGE Electric Grid Disturbances AND ELECTRIC GRID DISTURBANCES and the following:

Over-excitation.

EK1 .02 -Knowledge of the operational 295031 Reactor Low Water implications of the following concepts as Level/ 2 x they apply to REACTOR LOW WATER LEVEL: Natural circulation:

Plant-Specific EK1 .03 -Knowledge of the operational 295038 High Off-site Release implications of the following concepts as Rate 19 x they apply to HIGH OFF-SITE RELEASE RATE: Meteorological effects on off-site release. AK2.01 -Knowledge of the interrelations 295018 Partial or Complete between PARTIAL OR COMPLETE x LOSS OF COMPONENT COOLING Loss of CCW I 8 WATER and the following:

System loads AK2.01 -Knowledge of the interrelations 295016 Control Room between CONTROL ROOM Abandonment I 7 x ABANDONMENT and the following:

Remote shutdown panel: Plant-Specific AK2.04 -Knowledge of the interrelations 600000 Plant Fire On-site I 8 x between PLANT FIRE ON SITE and the following:

Breakers, relays, and Imp. Q# 3.9 76 4.6 77 3.6 78 4.4 79 4.2 80 4.7 81 4.2 82 3.3 39 3.8 40 2.8 41 3.3 42 4.4 43 2.5 44 ES-401 2 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions

-Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A 1 A2 G KIA Topic(s) disconnects AK3.04 -Knowledge of the reasons for 295005 Main Turbine Generator x the following responses as they apply to Trip/ 3 MAIN TURBINE GENERATOR TRIP: Main oenerator trip EK3.03 -Knowledge of the reasons for 295037 SCRAM Conditions the following responses as they apply to Present and Reactor Power x SCRAM CONDITION PRESENT AND Above APRM Downscale or REACTOR POWER ABOVE APRM Unknown/ 1 DOWNSCALE OR UNKNOWN: Lowerino reactor water level AK3.01 -Knowledge of the reasons for 295019 Partial or Complete the following responses as they apply to x PARTIAL OR COMPLETE LOSS OF Loss of Instrument Air I 8 INSTRUMENT AIR: Backup air system supply: Plant-Specific AA 1.03 -Ability to operate and/or 295003 Partial or Complete monitor the following as they apply to x PARTIAL OR COMPLETE LOSS OF Loss of AC/ 6 A.C. POWER: Systems necessary to assure safe plant shutdown EA 1.07 -Ability to operate and/or 295025 High Reactor Pressure I x monitor the following as they apply to 3 HIGH REACTOR PRESSURE:

ARl/RPT/ATWS:

Plant-Specific AA 1.03 -Ability to operate and/or 295004 Partial or Complete x monitor the following as they apply to Loss of DC Power I 6 PARTIAL OR COMPLETE LOSS OF D.C. POWER: A.C. electrical distribution EA2.02 -Ability to determine and/or 295028 High Drywell x interpret the following as they apply to Temperature I 5 HIGH DRYWELL TEMPERATURE:

Reactor pressure AA2.04 -Ability to determine and/or 295006 SCRAM / 1 x interpret the following as they apply to SCRAM: Reactor pressure AA2.01 -Ability to determine and/or 295021 Loss of Shutdown x interpret the following as they apply to Cooling/ 4 LOSS OF SHUTDOWN COOLING: Reactor water heatup/cooldown rate 2.2.22 -Equipment Control: Knowledge 295023 Refueling Accidents I 8 x of limiting conditions for operations and safety limits. 2.1.23 -Conduct of Operations:

Ability 295030 Low Suppression Pool x to perform specific system and Water Level I 5 integrated plant procedures during all modes of plant operation.

295026 Suppression Pool High x 2.2.12 -Equipment Control: Knowledge Water Temperature I 5 of surveillance procedures.

EK2.11 -Knowledge of the interrelations 295024 High Drywell Pressure I x between HIGH DRYWELL PRESSURE 5 and the following:

Drywell spray (RHR) looic: Mark-1&11 AA2.04 -Ability to determine and/or 295001 Partial or Complete interpret the following as they apply to Loss of Forced Core Flow x PARTIAL OR COMPLETE LOSS OF Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION:

Individual jet pump flows: Not-BWR-1

&2 KIA Category Totals: 3 4 3 3 4/3 3/4 Group Point Total: Imp. Q# 3.2 45 4.1 46 3.3 47 4.4 48 4.1 49 3.4 50 3.8 51 4.1 52 3.5 53 4.0 54 4.3 55 3.7 56 4.2 57 3.0 58 I 2017 ES-401 3 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions

-Tier 1 Group 2 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) EA2.04 -Ability to determine and/or 500000 High Containment interpret the following as they apply to x HIGH PRIMARY CONTAINMENT Hydrogen Concentration I 5 HYDROGEN CONCENTRATIONS:

Combustible limits for wetwell 2.1.7 -Conduct of Operations:

Ability to 295002 Loss of Main evaluate plant performance and make Condenser Vacuum I 3 x operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

EA2.02 -Ability to determine and/or 295035 Secondary interpret the following as they apply to Containment High Differential x SECONDARY CONTAINMENT HIGH Pressure 15 DIFFERENTIAL PRESSURE:

Off-site release rate: Plant-Specific AK1 .05 -Knowledge of the operational 295014 Inadvertent Reactivity implications of the following concepts as Addition x they apply to INADVERTENT REACTIVITY ADDITION:

Fuel thermal limits AK2.05 -Knowledge of the interrelations 295010 High Drywell Pressure I x between HIGH DRYWELL PRESSURE 5 and the following:

Drywell cooling and ventilation AK3.03 -Knowledge of the reasons for 295007 High Reactor Pressure x the following responses as they apply to /3 HIGH REACTOR PRESSURE:

RCIC operation:

Plant-Specific EA 1.03 -Ability to operate and/or 295033 High Secondary monitor the following as they apply to Containment Area Radiation x HIGH SECONDARY CONTAINMENT Levels/ 9 AREA RADIATION LEVELS: Secondary containment ventilation EA2.02 -Ability to determine and/or 295032 High Secondary interpret the following as they apply to Containment Area Temperature x HIGH SECONDARY CONTAINMENT 15 AREA TEMPERATURE:

Equipment operability 295035 Secondary 2.4.1 -Emergency Procedures I Plan: Containment High Differential x Knowledge of EOP entry conditions and Pressure/

5 immediate action steps. AK2.01 -Knowledge of the interrelations 2950201nadvertent x between INADVERTENT Containment Isolation I 5 & 7 CONTAINMENT ISOLATION and the following:

Main steam system KIA Category Totals: 1 2 1 1 1/2 1/1 Group Point Total: Imp. Q# 3.3 83 4.7 84 4.1 85 3.7 59 3.7 60 3.4 61 3.8 62 3.3 63 4.6 64 3.6 65 I 7/3 ES-401 System #I Name K K K 1 2 3 300000 Instrument Air 209001 LPCS 211000 SLC 217000 RCIC 206000 HPCI 264000 EDGs x 206000 HPCI x 203000 RHR/LPCI:

Injection x Mode 215004 Source Range x Monitor 4 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Plant Systems -Tier 2 Group 1 K K K A A2 A A G 4 5 6 1 3 4 A2.01 -Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those x predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Air dryer and filter malfunctions A2.09 -Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based x on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Low suppression pool level 2.4.6 -Emergency Procedures I x Plan: Knowledge of EOP mitigation strateaies.

2.1.25 -Conduct of Operations:

x Ability to interpret reference materials, such as graphs, curves, tables, etc. A2.09 -Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) x based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Low condensate storacie tank level: BWR-2,3,4 K1 .04 -Knowledge of the physical connections and/or cause-effect relationships between EMERGENCY GENERATORS (DIESEUJET) and the following:

Emergency generator cooling water svstem K1 .09 -Knowledge of the physical connections and/or cause-effect relationships between HIGH PRESSURE COOLANT INJECTION SYSTEM and the following:

ECCS keep fill system: BWR-2,3,4(P-Spec)

K2.01 -Knowledge of electrical power supplies to the following:

Pumps K2.01 -Knowledge of electrical power supplies to the following:

SRM channels/detectors Imp. Q# 2.8 86 3.3 87 4.7 88 4.2 89 3.7 90 3.2 1 4.0 2 3.5 3 2.6 4 ES-401 System #I Name K K K 1 2 3 223002 PCIS/Nuclear Steam x Supply Shutoff 205000 Shutdown Cooling x 239002 SRVs 259002 Reactor Water Level Control 209001 LPCS 262001 AC Electrical Distribution 300000 Instrument Air 262002 UPS (AC/DC) 261000 SGTS 4 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Plant Systems -Tier 2 Group 1 K K K A A2 A A G 4 5 6 1 3 4 K3.03 -Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on following:

Off-site radioactive release rates K3.02 -Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have on following:

Reactor water level: Plant-Specific K4.08 -Knowledge of RELIEF/SAFETY VALVES design feature(s) and/or x interlocks which provide for the following:

Opening of the SRV from either an electrical or mechanical signal K4.14 -Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM design x feature(s) and/or interlocks which provide for the following:

Selection of various instruments to provide reactor water level input K5.04 -Knowledge of the operational implications of the x following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM: Heat removal (transfer) mechanisms K5.02 -Knowledge of the operational implications of the x following concepts as they apply to A.C. ELECTRICAL DISTRIBUTION:

Breaker control K6.03 -Knowledge of the effect that a loss or malfunction of the x following will have on the INSTRUMENT AIR SYSTEM: Temperature indicators K6.03 -Knowledge of the effect that a loss or malfunction of the x following will have on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.):

Static inverter A 1.02 -Ability to predict and/or monitor changes in parameters x associated with operating the STANDBY GAS TREATMENT SYSTEM controls including:

Primary containment pressure Imp. Q# 3.6 5 3.2 6 3.6 7 3.4 8 2.8 9 2.6 10 2.7 11 2.7 12 3.1 13 ES-401 System # I Name K K K 1 2 3 211000 SLC 263000 DC Electrical Distribution 215003 IRM 217000 RCIC 215005 APRM I LPRM 212000 RPS 400000 Component Cooling Water 218000ADS 300000 Instrument Air 4 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Plant Systems -Tier 2 Group 1 K K K A A2 A A G 4 5 6 1 3 4 A 1.09 -Ability to predict and/or monitor changes in parameters x associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including:

SBLC system lineup A2.02 -Ability to (a) predict the impacts of the following on the D.C. ELECTRICAL DISTRIBUTION; and (b) based x on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Loss of ventilation durinQ charqinQ A2.01 -Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM; and (b) based on those predictions, x use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Power supply degraded A3.03 -Ability to monitor automatic operations of the x REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) including:

System pressure A3.05 -Ability to monitor automatic operations of the AVERAGE POWER RANGE x MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including:

Flow converter/comparator alarms A4.11 -Ability to manually x operate and/or monitor in the control room: Scram air header pressure A4.01 -Ability to manually x operate and/or monitor in the control room: CCW indications and control 2.1.27 -Conduct of Operations:

x Knowledge of system purpose and I or function.

2.4.35 -Emergency Procedures I Plan: Knowledge of local x auxiliary operator tasks during an emergency and the resultant operational effects. Imp. Q# 4.0 14 2.6 15 2.8 16 3.7 17 3.3 18 3.7 19 3.1 20 3.9 21 3.8 22 ES-401 System # I Name K K K 1 2 3 259002 Reactor Water Level Control 215003 IRM x 262001 AC Electrical Distribution x 262002 UPS (AC/DC) KIA Category Totals: 3 2 3 4 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Plant Systems -Tier 2 Group 1 K K K A A2 A A G 4 5 6 1 3 4 A 1.05 -Ability to predict and/or monitor changes in parameters associated with operating the x REACTOR WATER LEVEL CONTROL SYSTEM controls including:

FWRV/startup level control oosition:

Plant-Soecific K1 .07 -Knowledge of the physical connections and/or cause-effect relationships between INTERMEDIATE RANGE MONITOR (IRM) SYSTEM and the following:

Reactor vessel K3.01 -Knowledge of the effect that a loss or malfunction of the A.C. ELECTRICAL DISTRIBUTION will have on following:

Major svstem loads 2.1.28 -Conduct of Operations:

x Knowledge of the purpose and function of major system components and controls.

2 2 2 3 213 2 2 312 Group Point Total: Imp. Q# 2.9 23 3.0 24 3.5 25 4.1 26 I 26/5 ES-401 System #I Name K K K 1 2 3 215002 RBM 288000 Plant Ventilation 272000 Radiation Monitoring 245000 Main Turbine Generator and Auxiliary x Systems 230000 RHR/LPCI:

Torus/Pool Spray Mode 201002 RMCS x 219000 RHR/LPCI:

Torus/Pool Cooling Mode 234000 Fuel Handling Equipment 214000 RPIS 5 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Plant Systems -Tier 2 Group 2 K K K A A2 A A G 4 5 6 1 3 4 A2.03 -Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use x procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Loss of associated reference APRM channel: BWR-3,4,5 2.4.8 -Emergency Procedures I Plan: Knowledge of how x abnormal operating procedures are used in conjunction with EOP's. 2.2.38 -Equipment Control: x Knowledge of conditions and limitations in the facility license. K1 .02 -Knowledge of the physical connections and/or cause-effect relationships between MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS and the following:

Condensate system K4.09 -Knowledge of RHR/LPCI:

TORUS/SUPPRESSION POOL x SPRAY MODE design feature(s) and/or interlocks which provide for the following:

Spray flow cooling. K3.02 -Knowledge of the effect that a loss or malfunction of the REACTOR MANUAL CONTROL SYSTEM will have on following:

Rod block monitor: Plant-Specific K4.05 -Knowledge of RHR/LPCI:

TORUS/SUPPRESSION POOL x COOLING MODE design feature(s) and/or interlocks which provide for the following:

Pump minimum flow protection K5.02 -Knowledge of the operational implications of the x following concepts as they apply to FUEL HANDLING EQUIPMENT:

Fuel handling equipment interlocks K6.02 -Knowledge of the effect that a loss or malfunction of the x following will have on the ROD POSITION INFORMATION SYSTEM: Position indication probe Imp. Q# 3.3 91 4.5 92 4.5 93 2.5 27 3.0 28 2.9 29 3.0 30 3.1 31 2.7 32 ES-401 System # I Name K K K 1 2 3 241000 Reactor!Turbine Pressure Regulator 268000 Radwaste 288000 Plant Ventilation 204000 RWCU 201003 Control Rod and Drive Mechanism 290002 Reactor Vessel x Internals KIA Category Totals: 1 0 2 5 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Plant Systems -Tier 2 Group 2 K K K A A2 A A G 4 5 6 1 3 4 A 1.24 -Ability to predict and/or monitor changes in parameters associated with operating the x REACTOR!TURBINE PRESSURE REGULATING SYSTEM controls including:

Main turbine eccentricity A2.01 -Ability to (a) predict the impacts of the following on the RADWASTE; and (b) based on x those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

System rupture A3.01 -Ability to monitor automatic operations of the x PLANT VENTILATION SYSTEMS including:

Isolation/initiation sionals A4.07 -Ability to manually x operate and/or monitor in the control room: System temperature 2.4.31 -Emergency Procedures x I Plan: Knowledge of annunciator alarms, indications, or response procedures.

K3.06 -Knowledge of the effect that a loss or malfunction of the REACTOR VESSEL INTERNALS will have on following:

PCIS/NSSSS 2 1 1 1 1/1 1 1 1/2 Group Point Total: Imp. Q# 2.6 33 2.9 34 3.8 35 3.1 36 4.2 37 3.1 38 I 12/3 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility:

SSES LOC28 NRC Date: November 2016 Category KIA# RO SRO-Only Topic IR Q# IR Q# 2.1.42 Knowledge of new and spent fuel movement 3.4 94 procedures.

2.1.13 Knowledge of facility requirements for 3.2 99 controlling vital I controlled access. 1. 2.1.41 Knowledge of the refueling process. 2.8 66 Conduct Knowledge of industrial safety procedures of Operations 2.1.26 (such as rotating equipment, electrical, high 3.4 67 temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

Subtotal 2 2 2.2.20 Knowledge of the process for managing 3.8 95 troubleshooting activities.

2.2.6 Knowledge

of the process for making 3.6 98 changes to procedures.

Ability to manipulate the console controls as 2. 2.2.2 required to operate the facility between 4.6 68 Equipment shutdown and designated power levels. Control Knowledge of less than or equal to one hour 2.2.39 Technical Specification action statements for 3.9 69 systems. 2.2.43 Knowledge of the process used to track 3.0 74 inoperable alarms. Subtotal 3 2 2.3.11 Ability to control radiation releases.

4.3 96 Knowledge of radiation or containment 2.3.14 hazards that may arise during normal, 3.8 100 abnormal, or emergency conditions or activities.

2.3.4 Knowledge

of radiation exposure limits under 3.2 70 3. normal or emergency conditions.

Radiation Knowledge of radiation or containment Control 2.3.14 hazards that may arise during normal, 3.4 71 abnormal, or emergency conditions or activities.

Ability to use radiation monitoring systems, 2.3.5 such as fixed radiation monitors and alarms, 2.9 75 I portable survey instruments, personnel monitoring equipment, etc. Subtotal 3 2 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of EOP implementation hierarchy 2.4.16 and coordination with other support 4.4 97 procedures or guidelines such as, operating

4. procedures, AOPs and SAMGs. Emergency Procedures I 2.4.37 Knowledge of the lines of authority during 3.0 72 Plan implementation of the emergency plan. 2.4.17 Knowledge of EOP terms and definitions.

3.9 73 Subtotal 2 1 Tier 3 Point Total 10 7 ES-401 1 / 1 1 / 2 2 / 1 2 / 1 212 212 212 Record of Rejected K/As Form ES-401-4 Randomly Selected KIA 295027 High Containment Temperature 295011 High Containment Temperature 207000 Isolation (Emergency)

Condenser 209002 HPCS 201004 RSCS 201005 RCIS 239003 MSIV Leakage Control Reason for Rejection This topic applies to plants with Mark Ill containments only. The facility has a Mark II containment.

This topic applies to plants with Mark Ill containments only. The facility has a Mark II containment.

This system is not installed at the facility.

This system is not installed at the facility.

This system is no longer installed at the facility.

This system is not installed at the facility.

This system is no longer installed at the facility.

Question 57 The facility has a Mark-II containment, not a Mark-Ill.

295024 High Drywell Pressure Randomly resampled KIA 295024 High Drywell EK2.14 -Knowledge of the Pressure EK2.11 Knowledge of the 1 / 1 interrelations between HIGH interrelations between HIGH DRYWELL DRYWELL PRESSURE and the PRESSURE and the following:

Drywell spray following:

Containment (RHR) logic: Mark-1&11.

pressure:

Mark-II I Question 60 The facility has a Mark-II containment, not a Mark-Ill.

295010 High Drywell Pressure Randomly resampled KIA 295010 High Drywell AK2.03 -Knowledge of the Pressure AK2.05 -Knowledge of the 1 / 2 interrelations between HIGH interrelations between HIGH DRYWELL DRYWELL PRESSURE and the PRESSURE and the following:

Drywell cooling following:

Drywell/containment and ventilation.

differential pressure:

Mark-Ill Question 61 The facility does not have Isolation Condensers.

295007 High Reactor Pressure Randomly resampled KIA 295007 High Reactor AK3.01 -Knowledge of the Pressure AK3.03 -Knowledge of the reasons 1 / 2 reasons for the following for the following responses as they apply to responses as they apply to HIGH REACTOR PRESSURE:

RCIC operation:

HIGH REACTOR PRESSURE:

Plant-Specific.

Isolation condenser operation:

Plant-Specific Question 76 An acceptable question could not be written at 295030 Low Suppression Pool the SRO level for the randomly sampled KIA due to lack of relevant use of Drywell / Water Level Suppression Chamber differential pressure in EA2.04 -Ability to determine the facility's procedures and Technical and/or interpret the following as Specifications.

1 / 1 they apply to LOW Randomly resampled KIA 295030 Low SUPPRESSION POOL WATER LEVEL: Drywell/ suppression Suppression Pool Water Level EA2.02 -Ability to determine and/or interpret the following as chamber differential pressure:

they apply to LOW SUPPRESSION POOL Mark-1&11 WATER LEVEL: Suppression pool temperature.

Question 84 An acceptable question could not be written at 295002 Loss of Main the SRO level for the randomly sampled KIA Condenser Vacuum due to lack of applicable system limits and precautions related to Loss of Main Condenser 2.1.32 -Ability to explain and Vacuum. 1 / 2 apply all system limits and Randomly resampled KIA 295002 Loss of Main precautions.

Condenser Vacuum 2.1.7 -Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Question 88 An acceptable question could not be written at 211000 SLC the SRO level for the randomly sampled KIA due to lack of applicable EOP warnings, 2 / 1 2.4.20 -Knowledge of cautions, and notes related to SLC. operational implications of EOP Randomly resampled KIA 211000 SLC 2.4.6 -warnings, cautions, and notes. Knowledge of EOP mitigation strategies.

Question 94 The randomly sampled KIA is thoroughly and 2.1.45 -Ability to identify and more appropriately tested on the operating exam. 3 interpret diverse indications to validate the response of another Randomly resampled KIA 2.1.42 -Knowledge indicator.

of new and spent fuel movement procedures.

Question 22 An acceptable question could not be written at 300000 Instrument Air the RO level for the randomly sampled generic KIA with the given Tier 2 system. 2.4.41 -Knowledge of the Randomly resampled KIA 300000 Instrument 2 / 1 emergency action level Air 2.4.35 -Knowledge of local auxiliary thresholds and classifications.

operator tasks during an emergency and the resultant operational effects. Question 26 An acceptable question could not be written at 262002 UPS (AC/DC) the RO level for the randomly sampled generic KIA with the given Tier 2 system due to lack of 2.2.39 -Knowledge of less than appropriate less than one hour Technical one hour technical specification Specification action statements for UPS. 2 / 1 action statements for systems. Randomly resampled KIA 262002 UPS (AC/DC) 2.1.28 -Knowledge of the purpose and function of major system components and controls.

Question 28 An acceptable question could not be written for 230000 RHR/LPCI:

Torus/Pool the randomly sampled without overlapping Question 3. Spray Mode Randomly resampled KIA 230000 RHR/LPCI:

K2.02 -Knowledge of electrical Torus/Pool Spray Mode K4.09 -Knowledge of 212 power supplies to the following:

RHR/LPCI:

TORUS/SUPPRESSION POOL Pumps SPRAY MODE design feature(s) and/or interlocks which provide for the following:

Spray flow cooling. Question 37 An acceptable question could not be written the RO level for the randomly sampled generic 201003 Control Rod and Drive KIA. Additionally, the randomly sampled Mechanism generic KIA is already sampled in Question 93. 212 2.2.38 -Knowledge of Randomly resampled KIA 201003 Control Rod conditions and limitations in the and Drive Mechanism 2.4.31 -Knowledge of facility license. annunciator alarms, indications, or response procedures.

Question 39 An acceptable question could not be written for 700000 Generator Voltage and the randomly sampled KIA without testing GFE knowledge.

Electric Grid Disturbances Randomly resampled KIA 700000 Generator AK 1 . O 1 -Knowledge of the Voltage and Electric Grid Disturbances AK1 .02 operational implications of the -Knowledge of the operational implications of 212 following concepts as they the following concepts as they apply to apply to GENERATOR GENERATOR VOLTAGE AND ELECTRIC VOLTAGE AND ELECTRIC GRID DISTURBANCES and the following:

GRID DISTURBANCES and the Over-excitation.

following:

Definition of terms: volts, watts, amps, VARs, power factor Question 40 An acceptable question could not be written for 295031 Reactor Low Water the randomly sampled without overlapping Question 46. Level Randomly resampled KIA 295031 Reactor Low EK1 .03 -Knowledge of the Water Level EK1 .02 -Knowledge of the 1 I 1 operational implications of the operational implications of the following following concepts as they concepts as they apply to REACTOR LOW apply to REACTOR LOW WATER LEVEL: Natural circulation:

Plant-WATER LEVEL: Water level Specific.

effects on reactor power Question 41 An acceptable question could not be written for 295038 High Off-site Release the randomly sampled KIA without testing GET Rate I GFE knowledge.

EK1 .01 -Knowledge of the Randomly resampled KIA 295038 High Off-site Release Rate EK1 .03 -Knowledge of the 1 / 1 operational implications of the operational implications of the following following concepts as they concepts as they apply to HIGH OFF-SITE apply to HIGH OFF-SITE RELEASE RA TE: Meteorological effects on off-RELEASE RA TE: Biological site release. effects of radioisotope ingestion Question 47 An acceptable question could not be written for 295019 Partial or Complete the randomly sampled KIA due to lack of Service Air isolations related to loss of Loss of Instrument Air Instrument Air at this facility.

AK3.03 -Knowledge of the Randomly resampled KIA 295019 Partial or 1 / 1 reasons for the following Complete Loss of Instrument Air AK3.03 -responses as they apply to Knowledge of the reasons for the following PARTIAL OR COMPLETE responses as they apply to PARTIAL OR LOSS OF INSTRUMENT AIR: COMPLETE LOSS OF INSTRUMENT AIR: Service air isolations:

Plant-Backup air system supply: Plant-Specific.

Specific Question 59 An acceptable question could not be written for 295013 High Suppression Pool the randomly sampled generic KIA due to lack of procedural guidance regarding Suppression Temperature Pool stratification.

Additionally, Suppression AK1 .01 -Knowledge of the Pool temperature concepts are already operational implications of the sampled in Questions 56, 76, and 81. 1 / 2 following concepts as they Randomly resampled KIA 295014 Inadvertent apply to HIGH SUPPRESSION Reactivity Addition AK1 .05 -Knowledge of the POOL TEMPERATURE:

Pool operational implications of the following stratification concepts as they apply to INADVERTENT REACTIVITY ADDITION:

Fuel thermal limits. Question 67 The randomly sampled generic KIA is testing 2.1.31 -Ability to locate control extensively on, and better suited for, the room switches, controls, and operating exam. indications, and to determine Randomly resampled KIA 2.1.26 -Knowledge 3 that they correctly reflect the of industrial safety procedures (such as rotating desired plant lineup. equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

Question 69 The randomly sampled generic KIA is already 2.2.12 -Knowledge of sampled on the RO exam in Question 69. 3 surveillance procedures.

Randomly resampled KIA 2.2.39 -Knowledge of less than or equal to one hour Technical Specification action statements for systems. Question 70 An acceptable question could not be written for 2.3.11 -Ability to control the randomly sampled generic KIA without overlapping other questions on this exam or radiation releases.

previous 2 NRC exams. Additionally, the randomly sampled generic KIA is already 3 sampled in Question 96. Randomly resampled KIA 2.3.4 -Knowledge of radiation exposure limits under normal or emergency conditions.

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